Numerical simulation of current distribution in cable-in-conduit conductor for ITER TF coil

Hideki Kajitani*, Atsushi Ishiyama, Norikiyo Koizumi, Haruyuki Murakami, Hideo Nakajima

*この研究の対応する著者

研究成果: Article査読

3 被引用数 (Scopus)

抄録

The critical current of a cable-in-conduit conductor (CICC) for an ITER TF coil was measured using the SULTAN test facility. It was found that a non-uniform current distribution was established due to a non-uniform joint resistance. To evaluate the critical current performance accurately, we used a solder-filled joint. To study the effect of this solder-filled joint on the current distribution, we used a lumped circuit model and a distributed circuit model for the conductor and the joint, respectively, and combined the two to develop a new analysis model. This enabled us to solve the distributed circuit equation using only a few iterations, resulting in considerable reduction of the calculation time. Simulation results showed that, although the current distribution was non-uniform due to the ramping current, it improved at the current sharing temperature. This indicated that the solder-filled joint effectively improved the current distribution.

本文言語English
論文番号5654549
ページ(範囲)1964-1968
ページ数5
ジャーナルIEEE Transactions on Applied Superconductivity
21
3 PART 2
DOI
出版ステータスPublished - 2011 6

ASJC Scopus subject areas

  • 電子材料、光学材料、および磁性材料
  • 凝縮系物理学
  • 電子工学および電気工学

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